Authors:

The design objective of the lithium tokamak experiment (LTX) is to
investigate the equilibrium and stability of tokamak discharges with
near-zero recycling. The construction of LTX incorporates the
conversion of
the existing current drive experiment (CDX) vessel into one with
a nearly
complete plasma facing surface of liquid lithium This paper will
describe
the design, fabrication, and installation activities required to
convert CDX
into LTX. The most significant new feature is the addition of a
plasma
facing liner on a shell that will be operated at 300\r{ }C to
400\r{ }C and
covered with an evaporated layer of liquid lithium. The shell has
been
fabricated in-house from explosively bonded stainless steel on
copper to a
rather unique geometry to match the outer flux surface. Other
significant
device modifications include the construction of a new ohmic
heating power
system, rebuilding of the vacuum vessel, new lithium evaporators,
additional
diagnostics, modifications to the poloidal field coil geometry
and their
associated power supplies. Details on the progress of this
conversion will
be reported.

*Supported by US DOE contract \#DE-AC02-76CH-03073.

To cite this abstract, use the following reference: http://meetings.aps.org/link/BAPS.2006.DPP.VP1.14